Simulation study of power load with impurity seeding in advanced divertor "short super-X divertor" for a tokamak reactor

被引：12

作者：

Asakura, N. ^{[1
]}

Hoshino, K. ^{[1
]}

Shimizu, K. ^{[2
]}

Shinya, K. ^{[3
]}

Utoh, H. ^{[1
]}

Tokunaga, S. ^{[1
]}

Tobita, K. ^{[1
]}

Ohno, N. ^{[4
]}

机构：

[1] Japan Atom Energy Agcy, Rokkasho, Aomori 0393212, Japan

[2] Japan Atom Energy Agcy, Naka, Ibaraki 3110193, Japan

[3] Toshiba Nucl Engn Serv Co, Isogo Ku, Yokohama, Kanagawa 258523, Japan

[4] Nagoya Univ, Grad Sch Engn, Nagoya, Aichi 4648603, Japan

来源：

JOURNAL OF NUCLEAR MATERIALS | 2015年 / 463卷

关键词：

CONFIGURATION; DEMO;

D O I：

10.1016/j.jnucmat.2015.01.068

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

A short super-X divertor (SXD) is proposed as an option for the Demo divertor, where the field line length from the divertor null to the outer target was largely increased compared to a similar-size conventional divertor. Physics and engineering design studies for a 3 GW-level fusion power Demo reactor (SlimCS) (Tobita et al., 2009) have recently progressed. Minimal number of the divertor coils were installed inside the toroidal field coil, i.e. interlink-winding. Arrangement of the poloidal field coils and their currents were determined, taking into account of the engineering design such as vacuum vessel and the neutron shield structures, and the divertor maintenance scenario. Divertor plasma simulation showed that significant radiation region is produced between the super-X null and the target. Radiation loss in the divertor was increased, producing fully detached plasmas efficiently. Advantages of the short SXD were demonstrated, but the total peak heat load was a marginal level (10 MW m(-2)) for the engineering design. (C) 2015 Elsevier B.V. All rights reserved.

引用

页码：1238 / 1242

页数：5

共 13 条

[1] INVESTIGATION OF ADVANCED DIVERTOR MAGNETIC CONFIGURATION FOR DEMO TOKAMAK REACTOR [J].

Asakura, Nobuyuki ;

Shinya, Kichiro ;

Tobita, Kenji ;

Hoshino, Kazuo ;

Shimizu, Katsuhiro ;

Utoh, Hiroyasu ;

Someya, Youji ;

Nakamura, Makoto ;

Ohno, Noriyashu ;

Kobayashi, Masahiro ;

Tanaka, Hirohiko .

FUSION SCIENCE AND TECHNOLOGY, 2013, 63 (1T) :70-75

[2] A simulation study of large power handling in the divertor for a Demo reactor [J].

Asakura, Nobuyuki ;

Shimizu, Katsuhiro ;

Hoshino, Kazuo ;

Tobita, Kenji ;

Tokunaga, Shinsuke ;

Takizuka, Tomonori .

NUCLEAR FUSION, 2013, 53 (12)

[3] On heat loading, novel divertors, and fusion reactors [J].

Kotschenreuther, M. ;

Valanju, P. M. ;

Mahajan, S. M. ;

Wiley, J. C. .

PHYSICS OF PLASMAS, 2007, 14 (07)

[4] Consequences of a reduction of the upstream power SOL width in ITER [J].

Kukushkin, A. S. ;

Pacher, H. D. ;

Pacher, G. W. ;

Kotov, V. ;

Pitts, R. A. ;

Reiter, D. .

JOURNAL OF NUCLEAR MATERIALS, 2013, 438 :S203-S207

[5] Snowflake divertor plasmas on TCV [J].

Piras, F. ;

Coda, S. ;

Furno, I. ;

Moret, J-M ;

Pitts, R. A. ;

Sauter, O. ;

Tal, B. ;

Turri, G. ;

Bencze, A. ;

Duval, B. P. ;

Felici, F. ;

Pochelon, A. ;

Zucca, C. .

PLASMA PHYSICS AND CONTROLLED FUSION, 2009, 51 (05)

[6] Experimental divertor physics [J].

Pitcher, CS ;

Stangeby, PC .

PLASMA PHYSICS AND CONTROLLED FUSION, 1997, 39 (06) :779-930

[7] The magnetic field structure of a snowflake divertor [J].

Ryutov, D. D. ;

Cohen, R. H. ;

Rognlien, T. D. ;

Umansky, M. V. .

PHYSICS OF PLASMAS, 2008, 15 (09)

[8] Geometrical properties of a "snowflake" divertor [J].

Ryutov, D. D. .

PHYSICS OF PLASMAS, 2007, 14 (06)

[9] Advanced divertor configurations with large flux expansion [J].

Soukhanovskii, V. A. ;

Bell, R. E. ;

Diallo, A. ;

Gerhardt, S. ;

Kaye, S. ;

Kolemen, E. ;

LeBlanc, B. P. ;

McLean, A. ;

Menard, J. E. ;

Paul, S. F. ;

Podesta, M. ;

Raman, R. ;

Ryutov, D. D. ;

Scotti, F. ;

Kaita, R. ;

Maingi, R. ;

Mueller, D. M. ;

Roquemore, A. L. ;

Reimerdes, H. ;

Canal, G. P. ;

Labit, B. ;

Vijvers, W. ;

Coda, S. ;

Duval, B. P. ;

Morgan, T. ;

Zielinski, J. ;

De Temmerman, G. ;

Tal, B. .

JOURNAL OF NUCLEAR MATERIALS, 2013, 438 :S96-S101

[10] Compact DEMO, SlimCS: design progress and issues [J].

Tobita, K. ;

Nishio, S. ;

Enoeda, M. ;

Kawashima, H. ;

Kurita, G. ;

Tanigawa, H. ;

Nakamura, H. ;

Honda, M. ;

Saito, A. ;

Sato, S. ;

Hayashi, T. ;

Asakura, N. ;

Sakurai, S. ;

Nishitani, T. ;

Ozeki, T. ;

Ando, M. ;

Ezato, K. ;

Hamamatsu, K. ;

Hirose, T. ;

Hoshino, T. ;

Ide, S. ;

Inoue, T. ;

Isono, T. ;

Liu, C. ;

Kakudate, S. ;

Kawamura, Y. ;

Mori, S. ;

Nakamichi, M. ;

Nishi, H. ;

Nozawa, T. ;

Ochiai, K. ;

Ogiwara, H. ;

Oyama, N. ;

Sakamoto, K. ;

Sakamoto, Y. ;

Seki, Y. ;

Shibama, Y. ;

Shimizu, K. ;

Suzuki, S. ;

Takahashi, K. ;

Tanigawa, H. ;

Tsuru, D. ;

Yamanishi, T. ;

Yoshida, T. .

NUCLEAR FUSION, 2009, 49 (07)

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